ML19343C450
| ML19343C450 | |
| Person / Time | |
|---|---|
| Site: | National Bureau of Standards Reactor |
| Issue date: | 03/20/1981 |
| From: | Rozier Carter NATIONAL INSTITUTE OF STANDARDS & TECHNOLOGY (FORMERL |
| To: | |
| Shared Package | |
| ML19343C446 | List: |
| References | |
| NUDOCS 8103240233 | |
| Download: ML19343C450 (6) | |
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National Bureau of Standards Reactor Docket #50-184
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' Facility License No. TR-5 OPERATIONS REPORT-
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July,'1980 December, 1980
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?This report contains a summary of activities connected with the operations of the NBSR. It-is submitted in fulfillment of section 7.8d of.the NBSR; Technical Specifications ~and covers the period.from July 1,
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JSection numbers in this report (such as, ~ 7.8d(l)) correspond to those
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- 3. March 20, 1981.-
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ROBERT.-S.. CARTER-
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Chief,i Reactor Ra'iationd Division.
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TABLE OF CONTENTS
- 7.8d(l)- Summary of Plant Operations >
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7.8d(2) Unscheduled Shutdowns 7.8d(3)~ Tabulation of Major Items of Plant Maintenance-
- Tabulation of Major Changes-in the Facility and Procedures,
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. 7. 8d(4)
. and the . Test and Experiments, Carried Out Without Trior Approval
.by the U.-S. AEC (10 CFR 50.59)
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. 7.8d(5) Summary of Radioactive Material Released and Results of Environ- t
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l 7.8d(1) Summary of Plant Operations I During the period Jdly 1, 1980, through December 31, 1980,
, the reactor was critical for 2976.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> and the energy generated i
j was 29150.2 MWH.
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7.8d(2) Unscheduled Shutdowns
- October 5: Two reactor scrams because of commercial electrical power interruptions.
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Returned to power promptly.
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,7.8d(3) Tabulation of Major Items of Plant Maintenance
.l.' Replaced D 0 prefilter elements.
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- 2. c. hanged'diaphrams on suction and discharge valves of both Thermal
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4 Shield pumps.
- 3. ~ Changed diaphrams on Thermal Shield _IX' drain valves.
- 4. Installed'new door seal of B-2 elevator door. Also installed
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lower seal dogs. -
I l' 5. Repaired index plate pins for transfer arms B-5, L-5, E-2, I-2,
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D-3, -3, D-5, and'J-5.
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- 6. Changed Experimental Demin. IX resin.
7.- ' Replaced TSV-1 0-rings.
- 8. ' Changed diaphram on-Thermal Shield Heat Exchanger inlet valve.
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.9.~ l Changed Storage Pool IX after filters.
- 10. -- -Removed strainers from #1, 2, and 3 Secondary pump in preparation
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- 11. Repaired #6 Secondary pump suction valve.
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- 12. Moved Secondary pumps to new bedplate locations.
- 13. Changed both Thermal Shield IX resins.
i 14. Changed diaphram on TSV-17.
- 15. Replaced door seal regulator CAV-20.
-#3 D 0 pump.
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- 17. Removed broken springs from check valve on #3 D 20 pump discharge.
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l 18. Repair d'#1 Shim Arm shock.
~ 19. Installed pressure guages on Secondary pump headers.
- 20. Installed stainless steel ball valves on all Secondary drains,
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vents and guages.
. 21. Replaced #4 Secondary pump coupling and realigned pump / motor.
- 22. Changed 0-rings in RT-3 rabbit receiver and replaced section of flight 11ne between receiver and switch.
- 23. Removed, disassembled and repaired all-fuel transfer pickup tools"except E-2, I-2, B-5 and L-5.
j- . -24. Changed Storage Pool'prefilters.
- 25. Repaired Area Radiation Monitor Main Power Supply.
- 26. Replaced R/I-Amplifier on CO2 gas holder.
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- 27. Repaired intermittant grounding of annunciator panel- AN2.
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- 28. Replaced seven GM Tubes on the N16 monitor during this six-month period. _
- 29. -Replaced USE/ TRIP selector-switch on NC-3-Period Amplifier.
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- 30. Instrument Procedures Performed.
FIA-40 Reactor' Outlet flow LRC-1 Reactor Level Recorder LIA-40 Reactor Level Indicator NC-1 Low Count Rate Range Intermediate Range (Log N)
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NC-3
- NC-6 Power Level Range PC-3 ,
-Normal Exhaust System Press. Contr.
PC-27 Process Room Pressure Control SPC-150 Emergency Fan Control SPS-151 Vacuum Breaker Control.
RM-3-5 . Building Exhaust Radiation Monitor 7.8d(4) -Tabulation of Major Changes;in the Facility and Procedures, and the. Test and Experiments, Carried Out Without Prior
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Approval 1by the U. S. AEC -(10 CFR 50.59)
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Constructed replacement Cooling Tower and rearranged.
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- piping'*and pumpsfin the Secondary System for use in connection with the new tower.
- This modernization of the Secondary System involves
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' . component replacement and associated piping changes. The new.
-Cooling Tower conforms to'the Specifications of the Cooling-
. Tower Institute.and toLthe. applicable standards of ASTM.
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Piping conforms tofapplicable. ANSI Standards and all piping-
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- materials certified to: applicable ASTM Standards. The concrete
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1 basin complies'with the State of Maryland requirementstfor
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-highways,_ bridges'and; structures. : Electrical' equipment and f
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! connections were specified to conform to applicable NEMA Standards'and Federal Specifications.
, This Secondary System modernization program will improve 3 both performance and reliability. All of the functions of the
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old system, and more, will.be performed by the new system.
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Even though the Secondary System is not directly connected to
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any safetyffunction, it is= concluded'that there is no reduction
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1, - Secondary System procedures were revised accordingly to reflect
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the new system.
NOTE: Even though some of the work associated with this
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.c change carries into the next reporting period, it
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i- 7.8d(5)L Summary of Radioactive Material Released and Results of i
- . Environmental Surveys' Performed.
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Two hundred ninety-five-(295) curies of tritium and 226.
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curies'of Argon-41?were. released-as gaseous vaste,'while 226 millicuries'of= tritium and 491 microcuries'of other S-y emitters were released into the sanitary sewer. ,
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'C ? Environmental samples -of the streams, wells, vegetation l< and/or soil,' and air showed no significant changes.
- 7. 8d'(6) - ' Summary of Significant Exposures Re.ceived Ly Facility Personnel
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, L 1'. No significant exposures were received by any visitors.
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. 2.. (No:significant Exposures.were-received by facility-
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1 personnel for.this. period.-
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